| 1681 | Application of Adjoint Sensitivity Analysis Procedure to Single Phase Thermal-Hydraulics with Heat Structure Code 김민길; 이정익, 2018 한국원자력학회 추계학술발표회, 한국원자력학회, 2018-10-25 |
| 1682 | Application of Adjoint Sensitivity Analysis Procedure(ASAP) to Single Phase Thermal-Hydraulic System Analysis Code 김민길; 이원웅; 이정익, The Korean Nuclear Society Spring Meeting(2017), The Korean Nuclear Society, 2017-05-17 |
| 1683 | Application of an Integral Scaling Methodology to an Off-take Phenomenon at the Pressurizer Surge Line and its Validation Using RELAP5/MOD3.2 No, Hee Cheon; Kim, Hyoung Tae, 한국원자력학회 추계발표회, 한국원자력학회, 1999 |
| 1684 | Application of an integrated power line signal analysis methodology to the detection of major rotating machine abnormalities in nuclear power plants Jung, JC; Chang, YW; Seong, Poong-Hyun, NUCLEAR ENGINEERING AND DESIGN, v.229, no.2-3, pp.307 - 315, 2004-04 |
| 1685 | Application of an On-Line Fuzzy Learning Algorithm to Nuclear Steam Generator Level Control Park, Gee Y.; Seong, Poong-Hyun, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.70, pp.337 - 338, 1994 |
| 1686 | Application of Analytic Function Expansion Nodal Method to Analysis of MOX Assembly Loaded Reactor Cores Noh, J.M; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, pp.293 - 298, 1993-10 |
| 1687 | Application of APEC method in CANDU analysis Motalab, Mohammad Abdul; Kim, Woosong; Kim, Yonghee, International Conference on Physics of Reactors: Reactor Physics Paving the Way Towards More Efficient Systems, PHYSOR 2018, pp.3127 - 3141, Sociedad Nuclear Mexicana, A.C., 2018-04 |
| 1688 | Application of Artificial Neural Networks in Decommissioning Site Surveys Yim Man-Sung; Jun Li, Transactions of the American Nuclear Society, v.87, no.2002, pp.305 -, American Nuclear Society, 2002-11 |
| 1689 | Application of artificial neural networks to CPCS axial power distribution synthesis = 인공신경망 기반 노심보호계통 축방향 출력분포 합성 방법론 연구link Choi, Young Jae; 최영재; et al, 한국과학기술원, 2015 |
| 1690 | Application of Bayesian Network Considering the Special Dependency to Stochastic Events Lee, Kun Jai, Int'l Conf. on Probabilistic Safety Asssessment and Management(PSAM 7), 2004 |
| 1691 | Application of bayesian network methodology to the probabilistic risk assessment of nuclear waste disposal facility = 원자력 폐기물처분시설의 확률론적 리스크 평가에 대한 베이지안 망 방법론 적용link Lee, Chang-Ju; 이창주; et al, 한국과학기술원, 2006 |
| 1692 | Application of Bayesian network to the probabilistic risk assessment of nuclear waste disposal Lee, CJ; Lee, Kun Jai, RELIABILITY ENGINEERING & SYSTEM SAFETY, v.91, no.5, pp.515 - 532, 2006-05 |
| 1693 | Application of Bayesian statistics to infer radioactivity of uranium wastes 류지창; 홍정환; 박정석; 조규성, 2022 춘계 방사성폐기물학회, 한국방사성폐기물학회, 2022-05-26 |
| 1694 | Application of Communication Error Analysis Method (CEAM) 이승민; 김지태; 성풍현, 한국원자력학회 2010 추계학술발표대회, 한국원자력학회, 2010-10-21 |
| 1695 | Application of Complementary Indicators for the Performance Assessment of Disposal Facility in Korea 조용흠; 한솔찬; 윤종일, 2018 한국방사성폐기물학회 춘계학술발표회, Korean Radioactive Waste Society, 2018-06-01 |
| 1696 | Application of Complementary Indicators to Long-term Performance Assessment of Deep Geological Disposal Yun, Jong-Il, 13th International Conference on Probabilistic Safety Assessment and Management (PSAM), International Association for PSAM, 2016-10-06 |
| 1697 | Application of computational fluid dynamics codes for nuclear reactor design You, Byung-Hyun; Moon, Jangsik; Jeong, Yong Hoon, International Electronic Journal of Nuclear Safety and Simulation, v.6, no.3, pp.226 - 233, 2015-09 |
| 1698 | Application of condition-based HRA method for a manual actuation of the safety features in a nuclear power plant Kang, Hyun Gook; Jang, SC, RELIABILITY ENGINEERING & SYSTEM SAFETY, v.91, no.6, pp.627 - 633, 2006-06 |
| 1699 | Application of Control Process Variables for Cyber Attack Detection and Diagnosis in NPPs Seong, Poong-Hyun; Lee, Chanyoung, 2019 ANS Winter Meeting & Expo, American Nuclear Society, 2019-11-20 |
| 1700 | Application of data driven modeling and sensitivity analysis of constitutive equations for improving nuclear power plant safety analysis code Oh, ChoHwan; Kim, Doh Hyeon; Lee, Jeong Ik, NUCLEAR ENGINEERING AND TECHNOLOGY, v.55, no.1, pp.131 - 143, 2023-01 |
